Nuclear reactor corii cooling arrangement

ABSTRACT

D R A W I N G A CORE COOLING SYSTEM FOR A NUCLEAR REACTOR HAVING A PLURALITY OF PRIMARY FLUID FLOW SYSTEMS. THE REACTOR COOLANT FLOW FROM THE PRIMARY SYSTEMS IS JOINED UPON ENTERING THE PRESSURE VESSEL. JOINTURE IS ACCOMPLISHED IN A COMMON CHAMBER CAUSING HIGH COOLANT FLOW VELOCITIES AT LOW STATIC PRESSURES. IF A PIPE RUPTURES IN ONE OF THE PRIMARY FLUID FLOW SYSTEMS, THE LOW PRESSURE IN THE COMMON CHAMBER MINIMIZES LEAKAGE FROM THE INTACT FLOW SYSTEMS. THIS ALLOWS CONTINUATION OF COLLANT FLOW THROUGH THE NUCLEAR CORE FOR A SUFFICIENT LENGTH OF TIE TO EFFECTIVELY ELIMINATE THE POSSIBILITY OF THERMAL DAMAGE.

DEFENSIVE PUBLICATION UNITED STATES PATENT OFFICE Published at the request of the applicant or owner in accordance with the Notice of Dec. 16, 1969, 869 (LG. 687. The abstracts 0|. Defensive Publication applications are identified by distinctly numbered series and are arranged chronologically. The heading of each abstract indicates the number of pages of specification, including claims and sheets of drawings contained in the application as originally filed. The tiles 0! these applications are available to the public for inspection and reproduction may he purchased for 30 cents a sheet.

Defensive Publication applications have not been examined as to the merits of alleged invention. The Patent Ofllce makes no assertion as to the novelty of the disclosed subject matter.

PUBLISHED APRIL 16, 197% 921 O.Gr. 867

T921,015 NUCLEAR REACTOR CORE COOLING ARRANGEMENT Arnold H. Redding, Export, Pa., assignor to Westinghouse Electric Corporation, Pittsburgh, Pa. Filed Sept. 13, 1972, Ser. No. 288,610 Int. Cl. G21c 15/18, 15/24 US. Cl. 176--38 5 Sheets Drawing. 15 Pages Specification A core cooling system for a nuclear reactor having a plurality of primary fluid flow systems. The reactor coolant flow from the primary systems is joined upon entering the pressure vessel. J ointure is accomplished in a common chamber causing high coolant flow velocities at low static pressures. If a pipe ruptures in one of the primary fluid flow systems, the low pressure in the common chamber minimizes leakage from the intact flow systems. This allows continuation of coolant flow through the nuclear core for a sufiicient length of time to eifectively eliminate the possibility of thermal damage.

April 16, 1974 A. H. REDDING I I T921,015

NUCLEAR REACTOR CORE COOLING ARRANGEMENT Filed Sept. 13, 1972 5 Sheets-Sheet 1 April 16, 1974 A. H. REDDING I NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Sheets-Shoot 2 Filed Sept. 13, 1972 OIVF April 16, 1974 I H REDDlNG TQZLGIS NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Sheets-Sheet 3 Filed Sept. 13. 1972 new.

A ril 16, 1974 Filed Sept. 13. 1972 PERCENT FLOW IOO A. H. REDDING T921,015

NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Shbets-Sheot 4 4 6 8 10 I2 I4 I6 l8 T I ME (S ECONDS) A ril 16, 1974 A. H. REDDING NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Shasta-Sheet 5 Filed Sept. 13. 1972 BOILING TEMPERATURE OF LIQUID SODIUM PEAK TEMPERATURE OF CLADDING A 5 G F E R U T A R E w G E m R D m D M m PL E SC W 6 mm mm H w %A AL R E F A Ho FAILURE TEMPERATURE OF FUEL, ELEMENT, CLADDING IOOO TIME (SECONDS) B G F 6 M D MD DA DL F W WW I OE D O L R S %W m wm U AE Q ER U I UEW FG T F 0 AM N O I REE ED ETG. E D P A TL E E w AC T V A R A R KT E N A0 M TM P E E a G R N wL M m% FF O O O m m EL mmPEmmaEmP 0 WWW O O m m IOOO TIME (SECONDS? 

